[en] The analytical data generated during the last three years within the 4th framework program of the European Community at VTT Chemical Technology concerning UO₂ dissolution under oxidising conditions have been modelled in the present work. The modelling work has been addressed to perform a kinetic study of the dissolution data generated by Ollila (1999) under oxidising conditions by using unirradiated uranium dioxide as solid sample. The average of the normalised UO₂ dissolution rates determined by using the initial dissolution data generated in all the experimental tests is (6.06 ± 3.64)* 10^-7 mol m^-2 d^-1. This dissolution rate agrees with most of the dissolution rates reported in the literature under similar experimental conditions. The results obtained in this modelling exercise show that the same bicarbonate promoted oxidative dissolution processes operate for uranium dioxide, as a chemical analogue of the spent fuel matrix, independently of the composition of the aqueous solution used. (orig.)